Nuclear Regulatory Commission June 2017 – Federal Register Recent Federal Regulation Documents

The U.S. Nuclear Regulatory Commission (NRC) received and is considering approval of an application filed by AREVA, Inc. on April 14, 2017. The application seeks NRC approval of the indirect transfer of Material License SNM-1227; Import License IW009; and Export Licenses XSNM3471, XSNM3551, XSNM3697, XSNM3747, XSOU8833, and XCOM1202, for the Richland, Washington Fuel Manufacturing Facility from AREVA SA, the current parent company of the license holder, to Electricite de France SA (EDF).

The U.S. Nuclear Regulatory Commission (NRC) has received an application for the renewal of operating license NPF-47, which authorizes Entergy Operations, Inc. (the applicant) to operate River Bend Station, Unit 1 (RBS). The renewed license would authorize the applicant to operate RBS for an additional 20-year period beyond the period specified in the current license. The current operating license for RBS expires at midnight on August 29, 2025.

The U.S. Nuclear Regulatory Commission (NRC) is amending its spent fuel storage regulations by revising the Holtec International (Holtec) HI-STORM Flood/Wind (FW) Multipurpose Canister (MPC) Storage System listing within the ``List of Approved Spent Fuel Storage Casks'' to include Amendment No. 3 to Certificate of Compliance (CoC) No. 1032. Amendment No. 3 revises authorized contents to allow burnup credit for fuel types in the MPC-37 and revises CoC Condition 8, which has been previously incorporated in Amendment No. 2 to CoC No. 1032.

The U.S. Nuclear Regulatory Commission (NRC) invites public comment on the renewal of Office of Management and Budget (OMB) approval for an existing collection of information. The information collection is entitled, ``NRC Form 354, Data Report on Spouse.''

The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an amendment to Renewed Facility Operating License No. DPR- 50 held by Exelon Generation Company, LLC (Exelon, the licensee) for the operation of Three Mile Island Nuclear Station (TMI), Units 1 and 2, located in Dauphin County, Pennsylvania. The proposed amendment would allow for changes to TMI's Radiological Emergency Plan Annex staffing levels to align with Exelon's standard fleet Emergency Response Organization (ERO) framework. In accordance with the Possession-Only License No. DPR-73 Post-Defueling Monitored Storage Safety Analysis Report for TMI, Unit 2, the emergency plan for Unit 1 is considered to encompass Unit 2. Therefore, an amendment to the Unit 2 license is not required. The NRC is issuing an environmental assessment (EA) and finding of no significant impact (FONSI) associated with the proposed license amendment.

The U.S. Nuclear Regulatory Commission (NRC) is advertising for nominations for the positions of Agreement State representative, nuclear medicine physicist, and Health Care Administrator on the Advisory Committee on the Medical Uses of Isotopes (ACMUI).

The U.S. Nuclear Regulatory Commission (NRC) is issuing a Confirmatory Order to Tilden Mining Company, L.C. (Tilden Mining) as a result of an agreement reached during an Alternative Dispute Resolution mediation session conducted on May 8, 2017. The mediation session was conducted to reach agreement on the corrective actions to be implemented by Tilden Mining in response to apparent violations involving the failure to implement a security program in accordance with NRC requirements. The Confirmatory Order documents the corrective action commitments made by Tilden Mining and is effective on July 14, 2017.

The U.S. Nuclear Regulatory Commission (NRC) invites public comment on the renewal of Office of Management and Budget (OMB) approval for an existing collection of information. The information collection is entitled, ``Grant and Cooperative Agreement Provisions.''

The U.S. Nuclear Regulatory Commission (NRC) is discontinuing the rulemaking activity, ``Decoupling an Assumed Loss of Offsite Power from a Loss-of-Coolant Accident'' (the LOOP/LOCA rulemaking), and denying the associated petition for rulemaking (PRM), PRM-50-77. The purpose of this action is to inform members of the public of the discontinuation of the rulemaking activity and the denial of the PRM, and to provide a brief discussion of the NRC's decision regarding the rulemaking activity and PRM. The rulemaking activity will no longer be reported in the NRC's portion of the Unified Agenda of Regulatory and Deregulatory Actions (the Unified Agenda).

The U.S. Nuclear Regulatory Commission (NRC) invites public comment on the renewal of Office of Management and Budget (OMB) approval for an existing collection of information. The information collection is entitled, ``Standard Specifications for the Granting of Patent Licenses.''

The U.S. Nuclear Regulatory Commission (NRC) is granting an exemption to allow a departure from the certification information of Tier 1 of the generic design control document (DCD) and is issuing License Amendment Nos. 78 and 77 to Combined Licenses (COLs), NPF-91 and NPF-92 for the Vogtle Electric Generating Plant (VEGP) Units 3 and 4, respectively. The COLs were issued to Southern Nuclear Operating Company (SNC), and Georgia Power Company, Oglethorpe Power Corporation, MEAG Power SPVM, LLC, MEAG Power SPVJ, LLC, MEAG Power SPVP, LLC, Authority of Georgia, and the City of Dalton, Georgia (the licensee) for construction and operation of the Vogtle Electric Generating Station (VEGP) Units 3 and 4, located in Burke County, Georgia. The granting of the exemption allows the changes to Tier 1 information asked for in the amendment. Because the acceptability of the exemption was determined in part by the acceptability of the amendment, the exemption and amendment are being issued concurrently.

The U.S. Nuclear Regulatory Commission (NRC) has issued a combined license (No. NPF-103) to Virginia Electric and Power Company (doing business as Dominion Virginia Power) for North Anna Unit 3. In addition, the NRC has prepared a Summary Record of Decision (ROD) that supports the NRC's decision to issue the above-named combined license.

The U.S. Nuclear Regulatory Commission (NRC) is issuing an environmental assessment (EA) and a finding of no significant impact regarding a request from American Centrifuge Operating, LLC (ACO or the licensee). ACO is authorized to possess and use special nuclear material (SNM), source material, and byproduct material at its Lead Cascade Facility (LCF) in Ohio under NRC License SNM-7003, issued in 2004. ACO requested the NRC's approval to ship radioactively contaminated and non-contaminated classified matter and waste from the LCF to the Nevada National Security Site (NNSS) operated by the U.S. Department of Energy (DOE). The classified matter and waste would be permanently buried at the NNSS. ACO operated the LCF on DOE's site in Piketon, Ohio, where a gaseous diffusion uranium enrichment plant had previously operated. The LCF was operated as a test facility using centrifuges to enrich uranium, and provided reliability, performance, cost and other data for use in deciding whether to construct and operate a commercial uranium enrichment plant at DOE's Piketon, Ohio, site.

The U.S. Nuclear Regulatory Commission (NRC) reviewed an application by the U.S. Department of Energy (DOE) for an amendment to Materials License No. SNM-2508, for the Three Mile Island 2 (TMI-2) independent spent fuel storage installation (ISFSI), located on the Idaho National Engineering Laboratory in Butte County, Idaho. The amendment revises the licensee delegation of authority in the license, the technical specifications, and the final safety analysis report. These documents currently delegate authority under the license to the Manager, DOE Idaho Operations Office. The amendment would replace that reference with the Deputy Manager, Idaho Cleanup Project in each of the documents.

The U.S. Nuclear Regulatory Commission (NRC) reviewed an application by the U.S. Department of Energy (DOE) for an amendment to Materials License No. SNM-2512, for the Idaho Spent Fuel Facility independent spent fuel storage installation (ISFSI), located on the Idaho National Engineering Laboratory in Butte County, Idaho. The amendment revises the licensee delegation of authority in the license, the technical specifications, and the final safety analysis report. These documents currently delegate authority under the license to the Manager, DOE Idaho Operations Office. The amendment would replace that reference with the Deputy Manager, Idaho Cleanup Project in each of the documents.

The U.S. Nuclear Regulatory Commission (NRC) is issuing an Order prohibiting Mr. Toby Lashley from involvement in NRC-licensed activities for a period of 1 year. The Order also requires Mr. Lashley to notify the NRC of any current involvement in NRC-licensed activities. Additionally, Mr. Lashley is required to notify the NRC of his first employment in NRC-licensed activities for a period of one year following the 1-year prohibition period.

The U.S. Nuclear Regulatory Commission (NRC) is granting an exemption to allow a departure from the certification information of Tier 1 of the generic design control document (DCD) and is issuing License Amendment No. 61 to Combined Licenses (COL), NPF-93 and NPF-94, respectively. The COLs were issued to South Carolina Electric & Gas Company and the South Carolina Public Service Authority, (both collectively referred to as the licensee) for construction and operation of the Virgil C. Summer Nuclear Station (VCSNS) Units 2 and 3, located in Fairfield County, South Carolina. The granting of the exemption allows the changes to Tier 1 information asked for in the amendment. Because the acceptability of the exemption was determined in part by the acceptability of the amendment, the exemption and amendment are being issued concurrently.

The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its spent fuel storage regulations by revising the NAC International (NAC), MAGNASTOR[supreg] Cask System listing within the ``List of approved spent fuel storage casks'' to include Amendment No. 7 to Certificate of Compliance (CoC) No. 1031. Amendment No. 7 provides a new Passive MAGNASTOR[supreg] Transfer Cask and associated Technical Specification (TS) changes in Appendices A and B, and updates Section 4.3.1(i) in Appendix A of the TSs to include revised seismic requirements. Clarifying (non-technical) changes were also made to Appendices A and B.